TY - GEN
T1 - Technology Development of a High-Capacity High-Assay Low-Enriched Uranium Transportation Concept
AU - Eidelpes, Elmar
AU - Jarrell, Josh
AU - Bertsch, Denise
AU - Hall, Robert
AU - Marshall, William
AU - Hom, Brian
AU - Adkins, Harold
N1 - Publisher Copyright:
© 2024 Pacific Basin Nuclear Conference, PBNC 2024. All rights reserved.
PY - 2024
Y1 - 2024
N2 - This paper discusses the technology development efforts that led to the development of a high-capacity high-assay low-enriched uranium (HALEU) transportation concept. In 2018, the Department of Energy tasked Idaho National Laboratory to investigate strategies to transport large quantities of HALEU. To complete this task, Idaho National Laboratory collaborated with Pacific Northwest National Laboratory and Oak Ridge National Laboratory. One of the project outcomes was a transportation concept of five individual Type B packages transported on a single legal-weight truck. The total payload capacity of this concept is 1,881 kg (4,149 lb) of HALEU in the form of uranium dioxide (UO2) powder. It utilizes an existing Type B packaging design carrying a novel fuel basket design with an incorporated flux trap. The basket can be loaded with 18 individual fuel canisters. The research collaboration investigated the U.S. certification potential of this concept, which included evaluating criticality safety, radiological safety, thermal safety, structural integrity, and confinement under hypothetical accident scenarios of transport. The results of these evaluations demonstrated a promising potential for the U.S. certification of this concept. Eventually, these efforts led to the pursuance and issuance of a U.S. patent, thus protecting the associated intellectual property. Current short-term goals include making this intellectual property available to private industry partners for licensing, directly supporting Department of Energy’s objectives of accelerating the commercialization of national-laboratory-generated intellectual property. Long-term research goals would include exploring the feasibility of transporting other uranium chemical forms (e.g., UF4) or refining operational procedures to load or unload the packagings.
AB - This paper discusses the technology development efforts that led to the development of a high-capacity high-assay low-enriched uranium (HALEU) transportation concept. In 2018, the Department of Energy tasked Idaho National Laboratory to investigate strategies to transport large quantities of HALEU. To complete this task, Idaho National Laboratory collaborated with Pacific Northwest National Laboratory and Oak Ridge National Laboratory. One of the project outcomes was a transportation concept of five individual Type B packages transported on a single legal-weight truck. The total payload capacity of this concept is 1,881 kg (4,149 lb) of HALEU in the form of uranium dioxide (UO2) powder. It utilizes an existing Type B packaging design carrying a novel fuel basket design with an incorporated flux trap. The basket can be loaded with 18 individual fuel canisters. The research collaboration investigated the U.S. certification potential of this concept, which included evaluating criticality safety, radiological safety, thermal safety, structural integrity, and confinement under hypothetical accident scenarios of transport. The results of these evaluations demonstrated a promising potential for the U.S. certification of this concept. Eventually, these efforts led to the pursuance and issuance of a U.S. patent, thus protecting the associated intellectual property. Current short-term goals include making this intellectual property available to private industry partners for licensing, directly supporting Department of Energy’s objectives of accelerating the commercialization of national-laboratory-generated intellectual property. Long-term research goals would include exploring the feasibility of transporting other uranium chemical forms (e.g., UF4) or refining operational procedures to load or unload the packagings.
KW - advanced reactor fuel
KW - High-assay low-enriched uranium
KW - transportation
UR - http://www.scopus.com/inward/record.url?scp=85211602303&partnerID=8YFLogxK
U2 - 10.13182/PBNC24-45106
DO - 10.13182/PBNC24-45106
M3 - Conference contribution
AN - SCOPUS:85211602303
T3 - Pacific Basin Nuclear Conference, PBNC 2024
SP - 220
EP - 229
BT - Pacific Basin Nuclear Conference, PBNC 2024
PB - American Nuclear Society
T2 - 2024 Pacific Basin Nuclear Conference, PBNC 2024
Y2 - 7 October 2024 through 10 October 2024
ER -